Published 1992 | Version v1
Journal article

Comparison of analyzed design-basis events to actual plant transients

  • 1. Westinghouse Savannah River Co., Aiken, SC (United States)

Description

Fitness-for-Service Guidelines have recently been developed to provide acceptance criteria and evaluation methods for assessment of the integrity of the Zr-2.5 Nb pressure tubes in operating Canada deuterium uranium (CANDU) reactors. The guidelines provide a methodology for the evaluation of specific conditions in a single tube, such as manufacturing and inservice generated flaws, hydride blisters formed at points of contact between a pressure tube and its calandria tube, and generic degradation of pressure tube properties in service. The guidelines are divided into three sections. The first section describes the requirements that must be met to qualify the tubes ofr continued service. The second section provides the material properties data-base information needed to carry out the assessments. The third section provides the technical basis for the acceptance criteria and evaluation procedures as well as justifications and descriptions of the data bases. The guidelines were issued to CANDU reactor operators for trial use and released to the Atomic Energy Control Board of Canada for review and comment in May 1991

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
66
Journal Page Range
p. 341-342.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
past, present, and future.
Acronym
Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction
Dates
15-20 Nov 1992.
Place
Chicago, IL (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24050986
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPARATIVE EVALUATIONS; DESIGN BASIS ACCIDENTS; HEAT EXCHANGERS; K REACTOR; LEAKS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; TRANSIENTS
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; EVALUATION; HEAVY WATER MODERATED REACTORS; PRODUCTION REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SPECIAL PRODUCTION REACTORS

Optional Information

Secondary number(s)
CONF-921102--.